Search Results - Mok, Yong-Kyoon

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  1. 1
    High-temperature steam oxidation and oxide crack effects of Zr-1Nb-1Sn-0.1Fe fuel cladding

    High-temperature steam oxidation and oxide crack effects of Zr-1Nb-1Sn-0.1Fe fuel cladding by Lee, Cheol Min, Mok, Yong-Kyoon, Sohn, Dong-Seong

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  2. 2
    Microstructural characteristics and different effects of 800–1200 °C preformed oxides on high-temperature steam oxidation of a zirconium alloy cladding

    Microstructural characteristics and different effects of 800–1200 °C preformed oxides on high-temperature steam oxidation of a zirconium alloy cladding by Lee, Cheol Min, Jeong, Hu Yeong, Yoon, Aram, Mok, Yong-Kyoon, Sohn, Dong-Seong

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  3. 3
    Study of mechanism of oxidation resistance enhancement induced by preformed oxide on zirconium alloys

    Study of mechanism of oxidation resistance enhancement induced by preformed oxide on zirconium alloys by Lee, Cheol Min, Han, Young-Soo, Mok, Yong-Kyoon, Sohn, Dong-Seong

    Published in Corrosion science
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  4. 4
    Microstructural analysis of preformed oxides on a zirconium alloy before and after subsequent oxidation at 1000–1200 °C

    Microstructural analysis of preformed oxides on a zirconium alloy before and after subsequent oxidation at 1000–1200 °C by Lee, Cheol Min, Jeong, Hu Young, Yoon, Aram, Mok, Yong-Kyoon, Sohn, Dong-Seong

    Published in Corrosion science
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  5. 5
    Analysis of EBSD image quality related to microstructure evolution in zirconium–niobium cladding to quantify the degree of recrystallization

    Analysis of EBSD image quality related to microstructure evolution in zirconium–niobium cladding to quantify the degree of recrystallization by Jung, Tae-Sik, Jang, Hun, Mok, Yong-Kyoon, Yoo, Jong-Sung

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  6. 6
    Short communication on “self-crack-healing behavior of oxide formed on a zirconium alloy cladding tube”

    Short communication on “self-crack-healing behavior of oxide formed on a zirconium alloy cladding tube” by Lee, Cheol Min, Kim, Gyeonghun, Sohn, Dong-Seong, Han, Young-Soo, Mok, Yong-Kyoon

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  7. 7
    In situ investigation of the oxidation of Zr–Nb–Cu alloy in high-temperature hydrogenated water

    In situ investigation of the oxidation of Zr–Nb–Cu alloy in high-temperature hydrogenated water by Kim, Taeho, Kim, Seunghyun, Lee, Chung-yong, Mok, Yong-kyoon, Kim, Ji Hyun

    Published in Corrosion science
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  8. 8
    Effect of pre-oxidation temperature on the ductility of a zirconium alloy cladding under simulated accident conditions

    Effect of pre-oxidation temperature on the ductility of a zirconium alloy cladding under simulated accident conditions by Lee, Cheol Min, Lee, Hee-Jae, Kim, Hyun-Gil, Mok, Yong-Kyoon, Han, Young-Soo, Sohn, Dong-Seong

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  9. 9
    Dynamic Charge Carrier Transport Behaviors in Zirconium Oxide for Nuclear Cladding Materials

    Dynamic Charge Carrier Transport Behaviors in Zirconium Oxide for Nuclear Cladding Materials by Park, Il-Kyu, Lee, Sang-Seok, Mok, Yong Kyoon, Jeon, Chan-Woo, Kim, Hyun-Gil

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  10. 10
    IN-PILE PERFORMANCE OF HANA CLADDING TESTED IN HALDEN REACTOR

    IN-PILE PERFORMANCE OF HANA CLADDING TESTED IN HALDEN REACTOR by KIM, HYUN-GIL, PARK, JEONG-YONG, JEONG, YONG-HWAN, KOO, YANG-HYUN, YOO, JONG-SUNG, MOK, YONG-KYOON, KIM, YOON-HO, SUH, JUNG-MIN

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  11. 11
    Dynamic Charge Carrier Transport Behaviors in Zirconium Oxide for Nuclear Cladding Materials

    Dynamic Charge Carrier Transport Behaviors in Zirconium Oxide for Nuclear Cladding Materials by Park, Il-Kyu, Lee, Sang-Seok, Mok, Yong Kyoon, Jeon, Chan-Woo, Kim, Hyun-Gil

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  12. 12
    IN-PILE PERFORMANCE OF HANA CLADDING TESTED IN HALDEN REACTOR

    IN-PILE PERFORMANCE OF HANA CLADDING TESTED IN HALDEN REACTOR by Kim, Hyun-Gil, Park, Jeong-Yong, Jeong, Yong-Hwan, Koo, Yang-Hyun, Yoo, Jong-Sung, Mok, Yong-Kyoon, Kim, Yoon-Ho, Suh, Jung-Min

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